小型液态金属反应堆在海洋条件下的应用分析
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- 英文论文题名：Research on small liquid metal reactor in marine conditions
- 论文作者：韩东 ; 赵仲震 ; 纪西胜 ; 姚婷
- 英文论文作者：HAN Dong ; ZHAO Zhong-zhen ; JI Xi-sheng ; YAO Ting ; Department of Fast Reactor Research and Design China Fast Reactor Research Center
- 年：2015
- 作者机构：中国原子能科学研究院快堆研究设计所;
- 论文关键词：小型液态金属反应堆 ; 海洋条件 ; 钠冷快堆(SFR) ; 铅铋快堆(LFR)
- 英文论文关键词：small liquid metal reactor ; marine conditions ; sodium fast reactor(SFR) ; lead-cooled fast reactors(LFR)
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第2册（核能动力分卷（上））
- 语种：中文
- 分类号：TL425
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：7
- 文件大小：398k
- 原文格式：O
- 会议级别：全国
摘要
小型模块化反应堆(SMRs)以其安全性能高、运行灵活、适应性强、多用途等优势,未来具有较为广阔的发展空间。本文论述了国内外当前的小型液态金属反应堆的现况,同时论述了当前小型模块化反应堆在海洋条件下的应用现况,分析了液态金属堆在海洋条件下的应用可行性,对比分析了不同种液态金属反应堆之间的差异,针对目前钠冷快堆发展的制约因素,提出利用超临界二氧化碳(S-CO_2)布雷顿循环、其他流体替换中间回路钠,以及和斯特林机发动机相契合的三种改进方案。
Small nuclear reactor has a broad space for development in the future due to its safety performance,flexible and adaptable,multi-purpose and other advantages.This paper analyses research status in home and out broad of small liquid metal reactor.And analysis of the feasibility of the application of small liquid metal reactor is discussed in marine conditions.Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects,severe safety.Constraints of the current development for small sodium fast reactor are analyzed.In this paper the three schemes,including Super Critical CO_2 Brayton Cycle,Stirling Engine and Selecting fluids for evaluation at SFR intermediate loops,are briefly introduced.In addition,the future of small sodium fast reactor development is also expected in this paper.
Small nuclear reactor has a broad space for development in the future due to its safety performance,flexible and adaptable,multi-purpose and other advantages.This paper analyses research status in home and out broad of small liquid metal reactor.And analysis of the feasibility of the application of small liquid metal reactor is discussed in marine conditions.Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects,severe safety.Constraints of the current development for small sodium fast reactor are analyzed.In this paper the three schemes,including Super Critical CO_2 Brayton Cycle,Stirling Engine and Selecting fluids for evaluation at SFR intermediate loops,are briefly introduced.In addition,the future of small sodium fast reactor development is also expected in this paper.
引文
[1]OECD/NEA Nuclear Science Committee,Handbook on Lead-bismuth Eutectic Alloy and Lead Properties,Materials Compatibility,Thermal-hydraulics and Technologies.NEA No.6195.,ed.edition.2007.
[2]Morita,K.,et al.Thermophysical Properties of Lead-Bismuth Eutectic Alloy for Use in Reactor Safety Analysis.in Second Meeting of the NEA Nuclear Science Committee Working Group on LBE Technology of the Working Party on Scientific Issues of the Fuel Cycle(WPFC)NEA Headquarters.2004.Issy-les-Moulineaux,France.
[3]Morita,K.,et al.,Thermophysical properties of lead-bismuth eutectic alloy in reactor safety analyses.Journal of Nuclear Science and Technology,2006.43(5):p.526-536.
[4]Sobolev,V.,Thermophysical properties of lead and lead-bismuth eutectic.Journal of Nuclear Materials,2007.362(2-3):p.235-247.
[5]Sobolev,V.P.,P.Schuurmans,and G.Benamati,Thermodynamic properties and equation of state of liquid lead and lead-bismuth eutectic.Journal of Nuclear Materials,2008.376(3):p.358-362.
[6]Sar,F.,Mhiaoui,S.,Gasser,J.G.,2007.Thermal conductivity of liquid lead-bismuth alloys,possible coolants for fourth generation spallation nuclear reactors.J Non-Cryst Solids,353(32-40),3622-3627.
[7]李石磊,铅冷反应堆系统安全分析程序的开发,2007,中国原子能科学研究院.
[8]Takahashi,M.Status and Prospect of Development of Lead-Alloy-Cooled Fast Reactor,in International Conference on Advances in Nuclear Science and Engineering in Conjunction with LKSTN.2007.
[9]Tucek,K.,J.Carlsson,and H.Wider,Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects,severe safety and economical issues.Nuclear Engineering and Design,2006.236(14-16):p.1589-1598.
[10]Zrodnikov,A.V.,et al.,SVBR-100 module-type fast reactor of the IV generation for regional power industry.Journal of Nuclear Materials,2011.415(3):p.237-244.
[11]Zrodnikov,A.V.,et al.,Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors.Progress in Nuclear Energy,2008.50(2-6):p.170-178.
[12]Takahashi,M.,S.Uchida,and Y.Kasahara,Design study on reactor structure of Pb-Bi-cooled direct contact boiling water fast reactor(PBWFR).Progress in Nuclear Energy,2008.50(2-6):p.197-205.
[13]Bortot,S.,et al.,Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator.Nuclear Engineering and Design,2011.241(8):p.3021-3031.
[2]Morita,K.,et al.Thermophysical Properties of Lead-Bismuth Eutectic Alloy for Use in Reactor Safety Analysis.in Second Meeting of the NEA Nuclear Science Committee Working Group on LBE Technology of the Working Party on Scientific Issues of the Fuel Cycle(WPFC)NEA Headquarters.2004.Issy-les-Moulineaux,France.
[3]Morita,K.,et al.,Thermophysical properties of lead-bismuth eutectic alloy in reactor safety analyses.Journal of Nuclear Science and Technology,2006.43(5):p.526-536.
[4]Sobolev,V.,Thermophysical properties of lead and lead-bismuth eutectic.Journal of Nuclear Materials,2007.362(2-3):p.235-247.
[5]Sobolev,V.P.,P.Schuurmans,and G.Benamati,Thermodynamic properties and equation of state of liquid lead and lead-bismuth eutectic.Journal of Nuclear Materials,2008.376(3):p.358-362.
[6]Sar,F.,Mhiaoui,S.,Gasser,J.G.,2007.Thermal conductivity of liquid lead-bismuth alloys,possible coolants for fourth generation spallation nuclear reactors.J Non-Cryst Solids,353(32-40),3622-3627.
[7]李石磊,铅冷反应堆系统安全分析程序的开发,2007,中国原子能科学研究院.
[8]Takahashi,M.Status and Prospect of Development of Lead-Alloy-Cooled Fast Reactor,in International Conference on Advances in Nuclear Science and Engineering in Conjunction with LKSTN.2007.
[9]Tucek,K.,J.Carlsson,and H.Wider,Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects,severe safety and economical issues.Nuclear Engineering and Design,2006.236(14-16):p.1589-1598.
[10]Zrodnikov,A.V.,et al.,SVBR-100 module-type fast reactor of the IV generation for regional power industry.Journal of Nuclear Materials,2011.415(3):p.237-244.
[11]Zrodnikov,A.V.,et al.,Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors.Progress in Nuclear Energy,2008.50(2-6):p.170-178.
[12]Takahashi,M.,S.Uchida,and Y.Kasahara,Design study on reactor structure of Pb-Bi-cooled direct contact boiling water fast reactor(PBWFR).Progress in Nuclear Energy,2008.50(2-6):p.197-205.
[13]Bortot,S.,et al.,Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator.Nuclear Engineering and Design,2011.241(8):p.3021-3031.